BECO-86-041, Forwards Sanitized Rev 0 to Mark I Wetwell to Drywell Vacuum Breaker Load Methodology & Rev 0 to Mark I Wetwell to Drywell Differential Pressure Load & Vacuum Breaker Response for Pilgrim Station Unit 1, Per 860123 Request
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| ML20202A853 | |
| Person / Time | |
|---|---|
| Site: | Pilgrim |
| Issue date: | 04/07/1986 |
| From: | Harrington W BOSTON EDISON CO. |
| To: | Zwolinski J Office of Nuclear Reactor Regulation |
| Shared Package | |
| ML20202A858 | List: |
| References | |
| BECO-86-041, BECO-86-41, NUDOCS 8604110070 | |
| Download: ML20202A853 (2) | |
Similar Documents at Pilgrim | |
|---|---|
Category:CORRESPONDENCE-LETTERS
MONTHYEARML20217N8911999-10-15015 October 1999
[Table view]Forwards Rept of Changes,Tests & Experiments at Pilgrim Nuclear Power Station for Period of 970422-990621,IAW 10CFR50.59(b).List of Changes Effecting Fsar,Encl ML20217D3951999-10-13013 October 1999 Forwards Request for Addl Info Re Util 990806 Submittal on USI A-46, Implementation Methodology Used at Pilgrim Nuclear Power Station, Per GL 87-02 ML20217E1581999-10-0808 October 1999 Forwards Insp Rept 50-293/99-05 on 990726-0905.Three Violations Noted & Being Treated as Ncvs.Violations Include Failure to Assure That Design Bases Correctly Translated Into Specifications ML20217C3151999-10-0606 October 1999 Forwards Scenario Package for Pilgrim Nuclear Power Station Nrc/Fema Evaluated Exercise Scheduled for 991207.Without Encl ML20217D5591999-10-0505 October 1999 Documents Pilgrim Nuclear Power Station Five Yr Survey of Main Breakwater.Survey Has Determined That Pilgrim Main Breakwater Is Intact & Remains Adequately Constructed to Perform Designed Safety Function ML20217C8051999-10-0505 October 1999 Forwards Proprietary Results of Audiologic Evaluations for Jp Giar,License SOP-10061-3.Attachment Clearly Shows Requirements for Operator Hearing Ability Are Met. Proprietary Info Withheld,Per 10CFR2.790(a)(6) ML20212J8301999-09-30030 September 1999 Informs of Completion of mid-cycle PPR of Pilgrim Nuclear Power Station.Staff Conducts Reviews for All Operating NPPs to Integrate Performance Info & to Plan Insp Activities at Facility Over Next Six Months ML20216J9961999-09-29029 September 1999 Forwards Resume of Person Identified as Acting RPM in Licensee to NRC Re Notification That Person Named in License Condition 11 of 20-07626-02,is No Longer Employed at Pilgrim Station.Resume Withheld,Per 10CFR2.790 ML20212F7871999-09-24024 September 1999 Advises That Util 990121 Application for Amend Being Treated as Withdrawn.Proposed Changes Would Have Modified Facility UFSAR Pertaining to Values for post-accident Containment Pressure Credited in Pilgrim Net Positive Head Analyses ML20212H1381999-09-23023 September 1999 Submits Info in Support of Request Filed on 990730 to Grant one-time Exemption from 10CFR50,App E,Authorizing Biennial Full Participation Emergency Preparedness Exercise to Be Conducted in 2002 Instead of 2001 ML20212H1441999-09-23023 September 1999 Withdraws 990121 Request for License Change Re Emergency Core Cooling Sys Net Positive Suction Head,Due to Incorrect Datum Preparation ML20212C2861999-09-16016 September 1999 Forwards SER Accepting Licensee 981123 Request for Relief RR-E1,RR-E5,RR-E6 Pursuant to 10CFR50.55a(a)(3)(i) & Request for Relief RR-E2,RR-E3 & RR-E4 Pursuant to 10CFR50.55a(a)(3)(ii) ML20216F3451999-09-16016 September 1999 Forwards Summary Rept Providing Results of ISI Conducted at PNPS on-line & Refueling Outage (RFO 12) ML20216E7111999-09-0909 September 1999 Forwards License Renewal Application Including Form NRC-398 & Form NRC-396 for Jp Giar,License SOP-10061-3.Without Encls ML20216E5891999-09-0707 September 1999 Forwards Copy of Pilgrim Station Organization Structure. Encl Refelcts Changes in Upper Mgt Level Structure.Changes Were Effective 990901 ML20211M4501999-09-0303 September 1999 Informs That Pilgrim Nuclear Power Station Plans to Conduct Full Participation Emergency Preparedness Exercise with Commonwealth of Ma on 991207,IAW 10CFR50,App E,Section IV.F.2 ML20211M9161999-08-31031 August 1999 Submits Review & Correction of Info in Reactor Vessel Integrity Database (Rvid),Version 2,re Pilgrim Station ML20211J8391999-08-30030 August 1999 Forwards Rev 1 to Provisional Decommissioning Trust Agreement for Plant,Changing Portions of Agreement to Permit Up to Two Distributions & Clarify Formula for Distribution ML20211H5701999-08-27027 August 1999 Forwards Insp Rept 50-293/99-04 on 990610-0725.Two Violations Identified Being Treated as non-cited Violations ML20211C3381999-08-19019 August 1999 Provides semi-annual LTP Update,Including Schedule, Commitment Descriptions,Progress Since Last Update & Summary of Changes.Rev Bars Indicate Changes in Status Since Last Submittal ML20210U7521999-08-18018 August 1999 Forwards from Massachusetts State Senator T Murray Opossing Merger Between Bec Energy & Commonwealth Energy Systems ML20210U6691999-08-18018 August 1999 Forwards from Massachusetts State Senator T Murray Opposing Merger Between Bec Energy & Commonwealth Energy Systems ML20210U5761999-08-18018 August 1999 Responds to Opposing Merger of Bec Energy & Commonwealth Energy Sys in Commonwealth of Massachusetts. Informs That for Sale,Nrc Responsible for Only Ensuring That Entergy Technically & Financially Qualified to Operate NPP ML20210U5151999-08-17017 August 1999 Forwards Notice of Withdrawal of Application for Approval of Indirect Transfer of FOL for Pilgrim in Response to .Approval No Longer Needed Since Beco Sold Interest in Pilgrim to EOI on 990713 ML20211B3841999-08-16016 August 1999 Forwards Response to NRC Second RAI Re Pressure Locking & Thermal Binding of SR power-operated Gate Valves ML20210U4831999-08-13013 August 1999 Forwards fitness-for-duty Program Performance Data Sheets for Period of 990101-0630,per 10CFR26.71(d) ML20210S0891999-08-0909 August 1999 Forwards Amend 11 to Indemnity Agreement B-48 Signed by Boston Edison Co & Entergy Nuclear Generation Co ML20210R6251999-08-0606 August 1999 Provides Supplementary Info on USI A-46 Implementation Methodology at Pilgrim Station,To Enable NRC to Perform Evaluation & Issuance of Plant Specific SER for Plant ML20210M9411999-08-0202 August 1999 Requests That NRC Treat Pending Actions Requested by Beco Prior to 990713,as Requests Made by Entergy.Ltr Requests That Minor Administrative Changes to License Amend 182 & Associated Ser, ,reflect 990713 Transfer ML20210H8761999-07-30030 July 1999 Requests That NRC Grant Exemption from Requirements of 10CFR50,App E,Section IV F,Which Would Authorize Rescheduling of 2001 Biennial Full Participation Emergency Preparedness Exercise for Pilgrim Station to 2002 ML20210H8661999-07-29029 July 1999 Provides Revised Response to GL 96-06 & Addresses NRC Insp Concern for Containment Penetration X-12.Info Submitted to Facilitate NRC Review & Closeout of Subject GL for Plant ML20216E2321999-07-26026 July 1999 Discusses GL 92-01,rev 1,suppl 1, Rv Structural Integrity. NRC Revised Info in Rvid & Releasing as Rvid Version 2 ML20216D4131999-07-22022 July 1999 Informs That J Conlon,License OP-11040-1,terminated Employment with Beco on 990703,per 10CFR50.74.Individual Will Not Participate in Util Licensed Operator Requalification Training Program ML20210E2231999-07-20020 July 1999 Discusses Arrangements Made by Dennis & M Santiago During 990615 Telephone Conversation for NRC to Inspect Licensed Operator Requalification Program at Pilgrim During Wk of 991004 ML20210C4151999-07-19019 July 1999 Informs That Util Intends to Submit Approx Eight Licensing Actions in FY00 & Eight in FY01,in Response to Administrative Ltr 99-02.Actions Are Not Expected to Generate Complex Reviews ML20210A9441999-07-14014 July 1999 Responds to Re Changes to Pilgrim Nuclear Power Station Physical Security Plan Identified as Issue 2,rev 14, Addendum 1,respectively.No NRC Approval Is Required IAW 10CFR54(p) ML20210F3711999-07-14014 July 1999 Informs NRC That Effective 990713,listed Pilgrim Station Security Plans Have Been Transferred from Boston Edison to Entergy & Are Still in Effect ML20209G2251999-07-0909 July 1999 Forwards Insp Rept 50-293/99-03 on 990419-0609.Five Severity Level IV Violations of NRC Requirements Identified & Being Treated as non-cited Violations,Consistent with App C. Several Individual Tagging Errors Occurred ML20209C4661999-07-0707 July 1999 Forwards SE Accepting Addendum on Proposed Change in Corporate Ownership Structure Involving Entergy Nuclear Generation Co ML20209C3851999-07-0606 July 1999 Forwards Redacted Draft of Decommissioning Trust Agreement Re Transfer of PNPS & NRC Operating License & Matls License from Boston Edison Co to Entergy Nuclear Generating Co ML20209C7761999-07-0606 July 1999 Submits Annual Summary Rept of Changes Made to QAP Description as Described in QA Manual,Vol Ii.Rept Covers Period of Jul 1998 Through June 1999.No Changes Made During Period ML20196J7251999-07-0101 July 1999 Informs of Completion of Licensing Action for GL 96-01, Testing of Safety-Related Logic Circuits, for Pilgrim Nuclear Power Station ML20209B9411999-06-30030 June 1999 Discusses Deferral of IGSCC Welds to RFO 13.Deferral of Welds to Refueling Outage 13 Does Not Impact Acceptable Level of Quality & Safety Per 10CFR50.55(a)(3)(i) Since Plant in Compliance W/Exam Percentage Requirements ML20209B9431999-06-30030 June 1999 Provides Formal Notification That Closing Date for Sale & Transfer of Pilgrim Station Scheduled to Occur on 990713. a Wang Will Be Verbally Notified of Time of Sale Closing ML20196H2381999-06-29029 June 1999 Forwards SER Denying Licensee 980820 Request for Alternative Under PRR-13,rev 2 for Use of Code Case N-522 During Pressure Testing of Containment Penetration Piping ML20209B9791999-06-29029 June 1999 Forwards Rev 13A to Pilgrims COLR for Cycle 13,IAW TS 5.6.5 Requirements.Rev 13A Provides cycle-specific Limits for Operating Pilgrim During Remainder of Cycle 13 ML20209A8761999-06-28028 June 1999 Forwards SER Authorizing Licensee 990317 Relief Request to Use ASME Code Case N-573 as Alternative to ASME Code Section XI Article IWA-4000 for Remainder of 10-year Interval Pursuant to 10CFR50.55a(a)(3)(i) ML20209A8701999-06-25025 June 1999 Responds to NRC Request for Info Re Y2K Readiness of Computer Sys at Nuclear Power Plants. Y2K Readiness Disclosure for Plant,Reporting Status of Facility Y2K Readiness Encl ML20210U5901999-06-25025 June 1999 Opposes Merger of Bec Energy & Commonwealth Energy Sys in Commonwealth of Massachusetts.Expresses Skepticism Re Claim by Companies That Consumers Will Benefit from Proposed Consolidation & four-year Freeze in Base Rates ML20209C3431999-06-22022 June 1999 Forwards Addendum 1,Rev 14 to Pilgrim Station Security Plan,Iaw 10CFR50.54(p)(2).Changes Proposed Have Been Implemented & Constitute Increase in Plant Defense Plan Commitments.Encl Withheld,Per 10CFR73.21 1999-09-09 Category:INCOMING CORRESPONDENCE MONTHYEARML20217N8911999-10-15015 October 1999
[Table view]Forwards Rept of Changes,Tests & Experiments at Pilgrim Nuclear Power Station for Period of 970422-990621,IAW 10CFR50.59(b).List of Changes Effecting Fsar,Encl ML20217C3151999-10-0606 October 1999 Forwards Scenario Package for Pilgrim Nuclear Power Station Nrc/Fema Evaluated Exercise Scheduled for 991207.Without Encl ML20217C8051999-10-0505 October 1999 Forwards Proprietary Results of Audiologic Evaluations for Jp Giar,License SOP-10061-3.Attachment Clearly Shows Requirements for Operator Hearing Ability Are Met. Proprietary Info Withheld,Per 10CFR2.790(a)(6) ML20217D5591999-10-0505 October 1999 Documents Pilgrim Nuclear Power Station Five Yr Survey of Main Breakwater.Survey Has Determined That Pilgrim Main Breakwater Is Intact & Remains Adequately Constructed to Perform Designed Safety Function ML20216J9961999-09-29029 September 1999 Forwards Resume of Person Identified as Acting RPM in Licensee to NRC Re Notification That Person Named in License Condition 11 of 20-07626-02,is No Longer Employed at Pilgrim Station.Resume Withheld,Per 10CFR2.790 ML20212H1441999-09-23023 September 1999 Withdraws 990121 Request for License Change Re Emergency Core Cooling Sys Net Positive Suction Head,Due to Incorrect Datum Preparation ML20212H1381999-09-23023 September 1999 Submits Info in Support of Request Filed on 990730 to Grant one-time Exemption from 10CFR50,App E,Authorizing Biennial Full Participation Emergency Preparedness Exercise to Be Conducted in 2002 Instead of 2001 ML20216F3451999-09-16016 September 1999 Forwards Summary Rept Providing Results of ISI Conducted at PNPS on-line & Refueling Outage (RFO 12) ML20216E7111999-09-0909 September 1999 Forwards License Renewal Application Including Form NRC-398 & Form NRC-396 for Jp Giar,License SOP-10061-3.Without Encls ML20216E5891999-09-0707 September 1999 Forwards Copy of Pilgrim Station Organization Structure. Encl Refelcts Changes in Upper Mgt Level Structure.Changes Were Effective 990901 ML20211M4501999-09-0303 September 1999 Informs That Pilgrim Nuclear Power Station Plans to Conduct Full Participation Emergency Preparedness Exercise with Commonwealth of Ma on 991207,IAW 10CFR50,App E,Section IV.F.2 ML20211M9161999-08-31031 August 1999 Submits Review & Correction of Info in Reactor Vessel Integrity Database (Rvid),Version 2,re Pilgrim Station ML20211J8391999-08-30030 August 1999 Forwards Rev 1 to Provisional Decommissioning Trust Agreement for Plant,Changing Portions of Agreement to Permit Up to Two Distributions & Clarify Formula for Distribution ML20211C3381999-08-19019 August 1999 Provides semi-annual LTP Update,Including Schedule, Commitment Descriptions,Progress Since Last Update & Summary of Changes.Rev Bars Indicate Changes in Status Since Last Submittal ML20211B3841999-08-16016 August 1999 Forwards Response to NRC Second RAI Re Pressure Locking & Thermal Binding of SR power-operated Gate Valves ML20210U4831999-08-13013 August 1999 Forwards fitness-for-duty Program Performance Data Sheets for Period of 990101-0630,per 10CFR26.71(d) ML20210S0891999-08-0909 August 1999 Forwards Amend 11 to Indemnity Agreement B-48 Signed by Boston Edison Co & Entergy Nuclear Generation Co ML20210R6251999-08-0606 August 1999 Provides Supplementary Info on USI A-46 Implementation Methodology at Pilgrim Station,To Enable NRC to Perform Evaluation & Issuance of Plant Specific SER for Plant ML20210M9411999-08-0202 August 1999 Requests That NRC Treat Pending Actions Requested by Beco Prior to 990713,as Requests Made by Entergy.Ltr Requests That Minor Administrative Changes to License Amend 182 & Associated Ser, ,reflect 990713 Transfer ML20210H8761999-07-30030 July 1999 Requests That NRC Grant Exemption from Requirements of 10CFR50,App E,Section IV F,Which Would Authorize Rescheduling of 2001 Biennial Full Participation Emergency Preparedness Exercise for Pilgrim Station to 2002 ML20210H8661999-07-29029 July 1999 Provides Revised Response to GL 96-06 & Addresses NRC Insp Concern for Containment Penetration X-12.Info Submitted to Facilitate NRC Review & Closeout of Subject GL for Plant ML20216D4131999-07-22022 July 1999 Informs That J Conlon,License OP-11040-1,terminated Employment with Beco on 990703,per 10CFR50.74.Individual Will Not Participate in Util Licensed Operator Requalification Training Program ML20210C4151999-07-19019 July 1999 Informs That Util Intends to Submit Approx Eight Licensing Actions in FY00 & Eight in FY01,in Response to Administrative Ltr 99-02.Actions Are Not Expected to Generate Complex Reviews ML20210F3711999-07-14014 July 1999 Informs NRC That Effective 990713,listed Pilgrim Station Security Plans Have Been Transferred from Boston Edison to Entergy & Are Still in Effect ML20209C7761999-07-0606 July 1999 Submits Annual Summary Rept of Changes Made to QAP Description as Described in QA Manual,Vol Ii.Rept Covers Period of Jul 1998 Through June 1999.No Changes Made During Period ML20209C3851999-07-0606 July 1999 Forwards Redacted Draft of Decommissioning Trust Agreement Re Transfer of PNPS & NRC Operating License & Matls License from Boston Edison Co to Entergy Nuclear Generating Co ML20209B9431999-06-30030 June 1999 Provides Formal Notification That Closing Date for Sale & Transfer of Pilgrim Station Scheduled to Occur on 990713. a Wang Will Be Verbally Notified of Time of Sale Closing ML20209B9411999-06-30030 June 1999 Discusses Deferral of IGSCC Welds to RFO 13.Deferral of Welds to Refueling Outage 13 Does Not Impact Acceptable Level of Quality & Safety Per 10CFR50.55(a)(3)(i) Since Plant in Compliance W/Exam Percentage Requirements ML20209B9791999-06-29029 June 1999 Forwards Rev 13A to Pilgrims COLR for Cycle 13,IAW TS 5.6.5 Requirements.Rev 13A Provides cycle-specific Limits for Operating Pilgrim During Remainder of Cycle 13 ML20209A8701999-06-25025 June 1999 Responds to NRC Request for Info Re Y2K Readiness of Computer Sys at Nuclear Power Plants. Y2K Readiness Disclosure for Plant,Reporting Status of Facility Y2K Readiness Encl ML20210U5901999-06-25025 June 1999 Opposes Merger of Bec Energy & Commonwealth Energy Sys in Commonwealth of Massachusetts.Expresses Skepticism Re Claim by Companies That Consumers Will Benefit from Proposed Consolidation & four-year Freeze in Base Rates ML20209C3431999-06-22022 June 1999 Forwards Addendum 1,Rev 14 to Pilgrim Station Security Plan,Iaw 10CFR50.54(p)(2).Changes Proposed Have Been Implemented & Constitute Increase in Plant Defense Plan Commitments.Encl Withheld,Per 10CFR73.21 ML20195G3721999-06-0707 June 1999 Informs That Proposed Indicators Failed QA Assessments for Digital Verification,Validation & Control of Software. Proposed Mod Can Be Completed on-line ML20195B5021999-05-27027 May 1999 Provides Suppl Info to 990203 Request of Beco That NRC Consent to Indirect Transfer of Control of Util Interest in License DPR-35.Request Described Proposed Merger of Bec Energy with Commonwealth Energy Sys ML20207D4681999-05-24024 May 1999 Provides Addl Info to That Included in Beco Ltr 98-123 Dtd 981001,addressing NRC Concerns Described in GL 96-06, Concerning Waterhammer in Reactor Bldg Closed Cooling Water Sys ML20195B9051999-05-20020 May 1999 Forwards Completed Renewal Applications for Listed Operators.Without Encls ML20206J4901999-05-0606 May 1999 Forwards Completed License Renewal Application,Including Forms NRC-398 & 396 for Sc Power,License OP-6328-3 ML20206P0711999-05-0606 May 1999 Forwards NRC Form 396, Certification of Medical Exam by Facility Licensee, for K Walz,License SOP-10886-1.Encl Withheld IAW 10CFR2.790(a)(6) ML20206D3621999-04-27027 April 1999 Informs NRC That Final Five Sys self-assessments Required to Fulfill Commitment Made in 980828 Response to Insp Rept 50-293/98-04 Were Completed on 990422.Completion Was Delayed by High Priority Refueling Outage 12 Preparatory Work ML20205R9871999-04-21021 April 1999 Forwards Affidavit of JW Yelverton of Entergy Nuclear Generation Co Supporting Request for Withholding Info from Rept on Audit of Financial Statements for Year Ended 971231. Pages 16 & 18 of Subj Rept Also Encl ML20207B0891999-04-20020 April 1999 Forwards e-mail Message from Constituent,J Riell Re Y2K Compliance of Nuclear Power Plant in Plymouth,Massachusetts. Copy of Article Entitled Nuke Plants May Not Be Y2K Ready Also Encl ML20206A2741999-04-16016 April 1999 Dockets Encl Ltr Which Was Sent to AL Vietti-Cook Re Condition of Approval of Transfer of License & License Condition for DPR-35.Encl Resolves Issues Between Attorney General of Commonwealth of Massachusetts & Applicants ML20205P9131999-04-16016 April 1999 Submits Applicant Consent to Listed Condition of Approval of Transfer of License & License Condition for License DPR-35 & Affirmatively Request That NRC Adopt Listed Language in Order ML20205P9271999-04-16016 April 1999 Withdraws Motion for Leave to Intervene & Petition for Summary Or,In Alternative,For Hearing.Requests That NRC Adopt Condition of Approval of Transfer of License & License Condition Agreed to Beco & Entergy Nuclear Generation Co ML20205Q9231999-04-15015 April 1999 Forwards Proprietary & non-proprietary Addl Info in Support of Request to Transfer of Plant FOL & Matls License to Entergy Nuclear Generation Co.Proprietary Info Withheld,Per 10CFR2.790 ML20205P9631999-04-15015 April 1999 Provides Attachments a & B in Support of Request for Transfer of Plant Operating License & NRC Matl License from Beco to Entergy Nuclear Generation Co as Submitted in Ref 1. Info Provided in Response to Request at 990413 Meeting ML20205H9281999-04-0707 April 1999 Requests Withdrawal of Uwua Locals 369 & 387 Unions Joint Intervention in Listed Matter ML20205F3731999-04-0202 April 1999 Submits Addl Info Provided in Support of Request for Transfer of Pilgrim Nuclear Power Station Operating License & Matls License.State of Ma Order Authorizing Divestiture & Copy of Financial Arrangement Encl ML20204H3771999-03-26026 March 1999 Informs That Local 387,Utility Workers Union of America,AFL- Cio Voted to Approve New Contract with Entergy Nuclear Generation Co & Voted to Accept Boston Edison Divestiture Agreement ML20205D4231999-03-24024 March 1999 Forwards Decommissioning Funding Rept for Pilgrim Nuclear Power Station,In Accordance with 10CFR50.75(f)(1) 1999-09-09 Category:UTILITY TO NRC MONTHYEARBECO-90-108, Forwards Anticipated Operator Licensing Exam Schedule Requested by Generic Ltr 90-07, Operator Licensing Natl Exam Schedule,1990-09-12012 September 1990
[Table view]Forwards Anticipated Operator Licensing Exam Schedule Requested by Generic Ltr 90-07, Operator Licensing Natl Exam Schedule, ML20059D6641990-08-30030 August 1990 Forwards Revised Emergency Plan Implementing Procedures,Per 10CFR50,App E,Section V.W/O Encl ML20059D6791990-08-30030 August 1990 Notifies That Two Remaining Actions for Implementation of SPDS at Plant Complete,Per .Spds Procedures Modified,Identifying Sampling Panel C-19 Return Valves to Operator BECO-90-100, Advises That Valve MO-1001-50 Cannot Be Shown to Meet 30-day Mission for PASS in post-accident Environ Due to Elevated Radiation Dose Rates.Util Currently Developing Solution to Allow PASS to Meet 30-day Availability Requirement1990-08-27027 August 1990 Advises That Valve MO-1001-50 Cannot Be Shown to Meet 30-day Mission for PASS in post-accident Environ Due to Elevated Radiation Dose Rates.Util Currently Developing Solution to Allow PASS to Meet 30-day Availability Requirement BECO-90-102, Forwards Fitness for Duty Program Performance Data for Jan- June 19901990-08-23023 August 1990 Forwards Fitness for Duty Program Performance Data for Jan- June 1990 BECO-90-095, Informs That Kn Taylor Permanently Reassigned to Nuclear Training Dept as of 900717.Taylor Will Remain in Position Which Does Not Require License Certification1990-08-0808 August 1990 Informs That Kn Taylor Permanently Reassigned to Nuclear Training Dept as of 900717.Taylor Will Remain in Position Which Does Not Require License Certification BECO-90-092, Forwards, Decommissioning Funding Rept, Per 10CFR50.33(k) & 50.75(b)1990-07-26026 July 1990 Forwards, Decommissioning Funding Rept, Per 10CFR50.33(k) & 50.75(b) ML20044B3111990-07-11011 July 1990 Responds to NRC Bulletin 90-001, Loss of Fill-Oil in Transmitters Mfg by Rosemount. Corrective Actions Include Replacement of Transmitters Identified in Suspect Lots & Implementation of Surveillance Program ML20044A7891990-06-19019 June 1990 Responds to Generic Ltr 90-04, Request for Info on Status of Licensee Implementation of Generic Safety Issues Resolved W/Imposition of Requirements or Corrective Actions. Table Listing Status of Each Issue Encl ML20043D7181990-05-31031 May 1990 Advises That Response to NRC 900426 Safety Evaluation Re Util 880804 & 890619 Responses to Generic Ltr 88-01 Will Be Sent on 901115 ML20043A8211990-05-15015 May 1990 Notifies of Change of Senior Operator Status for Cj Martin, Per 10CFR50.74.CJ Martin Will No Longer Participate in Licensed Operator Requalification Training Program ML20042F2211990-05-0101 May 1990 Advises That Scheduled Completion of SPDS Human Factors Validation Activities Scheduled for 900630 & Sys Availability Test by 900731 ML20043B3881990-05-0101 May 1990 Responds to Violations Noted in Insp Rept 50-293/90-05. Corrective actions:82 Excess Flow Check Valves Installed & Operability of Valves Verified by Performing Surveillance Testing ML20012F5601990-04-0202 April 1990 Responds to Generic Ltr 89-13 Re Svc Water Sys Problems Affecting safety-related Equipment.Util Instituted Biofouling Control Program in 1982 & Program Has Been Effectively Implemented at Plant & Complies W/Generic Ltr ML20012F3631990-03-30030 March 1990 Requests Temporary Waiver of Compliance from Requirements of Tech Spec Table 3.2.C-1, APRM Upscale Rod Block in Startup & Refuel Modes to Avoid Unnecessary Delay in Critical Path Surveillance Testing ML20012C6501990-03-15015 March 1990 Responds to Generic Ltr 90-01 Re Request for Voluntary Participation in NRC Regulatory Impact Survey.Completed Questionnaire for Applicable Areas Delineated in Survey Encl ML20012D1931990-03-15015 March 1990 Forwards Proposed Scope & Objectives of Annual Exercise 90-04-B Scheduled for 900618 Per Lazarus 890609 Ltr, Emergency Exercise Objective & Scenerio Guidelines. Exercise Will Test & Evaluate Util EPIPs ML20012C7191990-03-14014 March 1990 Forwards Explanation of Errors in 890707 Application Re Corrective Action Plan & Advises That Errors Do Not Affect Technical Basis on Which Exemption Granted.Util Corrective Action Plan Remains Unchanged ML20011F5381990-02-26026 February 1990 Responds to Violations Noted in Insp Rept 50-293/89-12 on 891002-1119.Corrective Actions:On 891109,operations Personnel Directed,Via Night Orders,To Be More Diligent W/ Tagout Documentation & Boundary Tagging Clarified ML20011F2301990-02-23023 February 1990 Notifies of Change in Status of Senior Licensed Operator. DW Gerlits Terminated Senior Reactor Operator License on 900201 But Will Retain Position as Senior Sys & Safety Analysis Engineer ML20006G1411990-02-23023 February 1990 Advises That Tj Mcdonough Reassigned Effective 900126. Individual Will No Longer Participate in Licensed Operator Requalification Training Program ML20011F6521990-02-21021 February 1990 Forwards Inservice Insp Plan for 1990 mid-cycle Spring Outage for Facility.Augmented Insp Will Be Performed for Three IGSCC Category a Welds Using Guidance in Generic Ltr 88-01 & Criteria in NRC Bulletin 88-08,Suppl 3 ML20011F4481990-02-20020 February 1990 Forwards Revised Operability Evaluation of Salt Svc Water Pumps for Plant.Evaluation Concludes That Salt Svc Water Pumps Operable & Requirements of Tech Spec 3.5.B.1 for Pumps Met ML20006G0051990-02-20020 February 1990 Forwards Update to long-term Plan,In Accordance W/Section V.A of Plan for Long-Term Program. Util Implementing Plant Betterment Mods & Activities ML20011E7551990-02-0909 February 1990 Requests Temporary Relief from Tech Spec 4.7.A.2.b.1.d, Limiting Condition for Operation. ML19354E7661990-01-23023 January 1990 Responds to NRC Bulletin 89-002, Stress Corrosion Cracking of High Hardness Type 410 Stainless Steel Bolting in Anchor Darling.... Review Determined That No Subj Anchor Darling Swing Check Valves or Similar Valves Installed at Facility ML20011F4441990-01-19019 January 1990 Forwards Operability Evaluation Re Salt Svc Water Pumps P208 B,C,D & E,Per 900117 Telcon.Evaluation Concluded That Salt Svc Water Pumps P208 B,C,D & E Operable & Tech Spec 3.5.B.1 Requirements Met ML20006A0761990-01-15015 January 1990 Forwards Executed Amend 10 to Indemnity Agreement B-48 ML20006A2591990-01-15015 January 1990 Responds to Generic Ltr 89-10, Safety-Related Motor- Operated Valve Testing & Surveillance. Util Will Develop Program to Enhance Maint,Analysis & Testing Already Conducted on motor-operated Valves ML20005G7701990-01-11011 January 1990 Discusses Revised Schedule for Operability & Availability of Spds,Per 891221 Notification to Nrc.Rev Necessitated by Software Problems Affecting 891231 Schedule Projected in Util 890710 Ltr ML20005G7451990-01-11011 January 1990 Provides Bases for Environ Qualification of Instrumentation Monitoring Effluent Radioactivity & Status of Standby Power Per Reg Guide 1.97,Rev 3 & Generic Ltr 82-33 ML20005G8061990-01-11011 January 1990 Advises That Commitment to Complete Enhancements of Control Panels as Part of Dcrdr,Per NUREG-0737,Item I.D.1 by Oct 1989 Not Met.All Three Panels at Simulator Enhanced & Installation of Revised Meter Scales in Progress ML20005F0761990-01-0404 January 1990 Forwards Revised Inservice Test Program in Response to Generic Ltr 89-04.List of Inservice Test Program Relief Requests Previously Submitted & Acceptable,Per Generic Ltr 89-04,encl ML20005E5601989-12-29029 December 1989 Certifies That Util Has Established Fitness for Duty Program That Meets Requirements of 10CFR26.Drug & Alcohol Level Screening Match Rule Imposition & Implementation Will Be Effective on 900103 ML20042D4821989-12-26026 December 1989 Responds to Violations Noted in Insp Rept 50-293/89-10. Corrective Action:Radiological Section Standing Order 89-09 Issued Allowing Only Radiological Supervisors to Exercise Locked High Radiation Area Door & Key Control ML20011D6851989-12-14014 December 1989 Forwards Response to Generic Ltr 89-21, Request for Info Re Status of Implementation of USI Requirements. ML20011D1631989-12-14014 December 1989 Forwards Pilgrim Nuclear Plant Station Final Assessment Rept, Summarizing Results of self-assessments & Evaluations Conducted Throughout Implementation of Plant Restart Plan & Power Ascension Program ML19325F2751989-11-10010 November 1989 Responds to NRC Bulletin 88-010,Suppl 1, Nonconforming Molded-Case Circuit Breakers. Util Installed H2/02 Analyzers Procured in 1980 & Therefore Exempt from Bulletin Requirements ML19327C0911989-11-0606 November 1989 Forwards Response to Suppl 3 to NRC Bulletin 88-008, Thermal Stresses in Piping Connected to Rcs. Since cyclic- Thermal Heatup/Cooldown Not Present in Piping,Failure Due to Cyclic Thermal Fatigue Will Not Occur ML19325E8581989-11-0101 November 1989 Discusses Litigation Before FERC Re Plant.Util Will Undertake Review of Matls Developed by Opposing Parties in Proceedings.Required Repts Will Be Submitted to NRC After Reportability Has Been Determined ML19325E5251989-10-27027 October 1989 Responds to Generic Ltr 88-20,Suppl 1,describing Plan for Completing Individual Plant Exam for Severe Accident Vulnerabilities.Performance of Level 1 PRA Based on Current Plant Design & Operation Intended ML19325E5661989-10-27027 October 1989 Response to Generic Ltr 89-04, Guidance on Developing Acceptable Inservice Testing Programs. Revised Inservice Testing Program Which Will Include Statement of Conformance to Technical Positions Will Be Submitted by 891215 ML19324B8191989-10-25025 October 1989 Informs That C Leonard & J Stokes Reassigned to Positions Which Do Not Require License Certification Effective 891003 & 891020,respectively ML19327B2291989-10-20020 October 1989 Responds to Generic Ltr 89-07 Re Power Reactor Safeguards Contingency Planning for Surface Vehicle Bombs.Changes Made to Contingency Plan,Per 10CFR50.54.Plan Withheld (Ref 10CFR73.21) ML19325E0981989-10-20020 October 1989 Responds to NRC Re Violations Noted in Insp Rept 50-293/89-07.Corrective Actions:Terminal Block Replaced, post-work Functional Test of Ref Temp Switches Performed & Procedure Tp 88-78 Revised to Correct Relay Numbers BECO-89-142, Responds to NRC Re Violations & Proposed Imposition of Civil Penalty from Insp Rept 50-293/89-95. Corrective Action:Two Responsible Util Operators Suspended Because Breakers Incorrectly Positioned for Test1989-09-22022 September 1989 Responds to NRC Re Violations & Proposed Imposition of Civil Penalty from Insp Rept 50-293/89-95. Corrective Action:Two Responsible Util Operators Suspended Because Breakers Incorrectly Positioned for Test BECO-89-144, Requests Interim Approval for Relief from Testing of RHR Sys Valves 63 & 64 Until Refueling Outage 8 Scheduled for 9103151989-09-22022 September 1989 Requests Interim Approval for Relief from Testing of RHR Sys Valves 63 & 64 Until Refueling Outage 8 Scheduled for 910315 BECO-89-135, Forwards Util Anticipated OL Exam Schedule,Per 890706 Generic Ltr 89-12 Request1989-09-11011 September 1989 Forwards Util Anticipated OL Exam Schedule,Per 890706 Generic Ltr 89-12 Request BECO-89-131, Forwards Tech Spec Figures 6.2-2 & 6.2-1,replacing Title of Director of Nuclear Engineering W/Title of Station Director & Adding New Title of Vice President of Nuclear Engineering1989-09-0505 September 1989 Forwards Tech Spec Figures 6.2-2 & 6.2-1,replacing Title of Director of Nuclear Engineering W/Title of Station Director & Adding New Title of Vice President of Nuclear Engineering BECO-89-129, Submits Addl Info Re 890707 Request for Exemption from Certain Containment Leakage Testing Requirements of 10CFR50. Plant mid-cycle Maint Outage,Previously Scheduled for Oct 1989,has Been Rescheduled for Spring 19901989-09-0101 September 1989 Submits Addl Info Re 890707 Request for Exemption from Certain Containment Leakage Testing Requirements of 10CFR50. Plant mid-cycle Maint Outage,Previously Scheduled for Oct 1989,has Been Rescheduled for Spring 1990 1990-09-12 |
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BDSTON EDisDN COMPANY -.
800 BOYLsTON STREET BOSTON. MASSACHUSETTS 02199 WILLIAM D. HARRtNGTON tamson vecs resotosur April 7, 1986 BECo 86-041 Mr. John A. Zwolinski, Director BWR Project Directorate #1 Division of Licensing Office of Nuclear Reactor Regulation U.S. Nuclear Regulatory Commission Washington, D. C. 20555 License DPR-35 Docket 50-293
Subject:
Modification of Vacuum Breakers
Dear Sir:
We are providing further information on our Vacuum Breaker Chugging Methodology as requested in your letter of January 23, 1986( BECo #1.86-021).
This information was provided in two (2) generic and one (1) plant specific documents which apparently were never docketed for Pilgrim Station. We are attaching two (2) of these three (3) reports. The third report "CDI Technical Memo 84-11" was transmitted directly to you by General Electric on November 6, 1984. A copy of their cover letter is also attached.
We trust this meets your needs to complete the review of the vacuum breaker issue.
Very truly yours, MTL/ns Attachments
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Attachment 1 Question 1: Is the chugging source rate used in the Pilgrim evaluation the same as the one developed in C.D.I. Report No. 84-3?
Response: Yes. The methodology followed in C.D.I. Report No. 84-3 (Ref. 1) is identical to the methodology used in the Pilgrim evaluation (Ref. 2) and detailed in response to question 5 from the NRC (Ref. 3).
Question 2: Did the Pilgrim calculation apply the 1.07 load factor to account for the uncertainty in calculating the underpressure?
Response: A load factor, used to assure conservative prediction of the underpressure and detailed in response to question 2 from the NRC (Ref. 3), was applied to the Pilgrim evaluation (Ref. 2). In fact the load factor used in the plant unique evaluation was 1.06 and yields a conservative prediction of the underpressure.
Question 3: Did the Pilgrim calculation use the drywell model which resulted in the most conservative prediction?
Response: Yes. Drywell modeling was examined in response to question 6 from the NRC (Ref. 3). For the Pilgrim evaluation (Ref. 2), the acoustic volume model results in a more conservative forcing function, and was therefore used.
References
- 1. " Mark I Wetwell to Drywell Vacuum Breaker Load Methodology, Revision 0,"
Continuum Dynamics, Inc. Report No. 84-3, February 1984.
- 2. " Mark I Wetwell to Drywell Differential Pressure Load and Vacuum Breaker Response for the Pilgrim Station Unit 1, Revision 0," Continuum Dynamics, Inc. Technical Note No. 84-15, January 1985.
- 3. " Response to NRC Request for Additional Information on Mark I Containment Program Wetwell to Drywell Vacuum Breaker Load Methodology Revision 0,"
Continuum Dynamics, Inc. Technical Note No. 84-11, October 1984.
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